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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
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Reactivity Effects of Large Voids in the Reflector of a Light-Water-Moderated and -Reflected Reactor
A. B. Reynolds, T. J. Thompson, K. M. Henry, E. B. Johnson
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE60-A25691
The Slowing Down of Neutrons by Deuterium
M. M. Levine, K. E. Roach, D. B. Wehmeyer, P. F. Zweifel
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 14-20
Technical Paper | doi.org/10.13182/NSE60-A25692
Steels for Nuclear Reactors
H. F. Beeghly
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 21-25
Technical Paper | doi.org/10.13182/NSE60-A25693
An Accurate Transfer Function for the Dynamic Analysis of Temperature and Heat Release in Cylindrical Fuel Elements
Modesto Iriarte, Jr.
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 26-32
Technical Paper | doi.org/10.13182/NSE60-A25694
Approximate Solutions of the Reactor Kinetic Equations for Ramp Inputs
John MacPhee
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 33-43
Technical Paper | doi.org/10.13182/NSE60-A25695
Enriched-Uranium Hydride Critical Assemblies
G. A. Linenberger, J. D. Orndoff, H. C. Paxton
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 44-57
Technical Paper | doi.org/10.13182/NSE60-A25696
Integral Transport Theory of Thermal Utilization Factor in Infinite Slab Geometry
Michel H. Theys
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 58-63
Technical Paper | doi.org/10.13182/NSE60-A25697
Space-Dependent Prompt Kinetics of a Subcritical Reactor
Joseph Agresta, Lyle B. Borst
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 64-68
Technical Paper | doi.org/10.13182/NSE60-A25698
An Approximate Method for Treating Neutron Slowing Down
Gerald Goertzel, Eugene Greuling
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 69-72
Technical Paper | doi.org/10.13182/NSE60-A25699
OMR Flat Plate Fuel Element Fabrication
G. V. Alm, E. E. Garrett, M. H. Binstock
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 73-82
Technical Paper | doi.org/10.13182/NSE60-A25700
Development of Centrifugal Pumps for Operation with Liquid Metals and Molten Salts at 1100–1500°F
A. G. Grindell, W. F. Boudreau, H. W. Savage
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 83-91
Technical Paper | doi.org/10.13182/NSE60-A25701
Effects of the Contamination by Light Water on Lattices of Natural Uranium Rods in Heavy Water
Bernard S. Finn, James W. Wade
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 93-96
Technical Paper | doi.org/10.13182/NSE60-A29076
Thermal Stresses in Nuclear Reactor Vessel Nozzles
J. S. Busch, A. J. Martenson, S. W. Sinderson, C. F. Peck, Jr.
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 97-103
Technical Paper | doi.org/10.13182/NSE60-A29077
Accuracy of the Sn Code in Cell Calculations
A. V. Campise
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 104-110
Technical Paper | doi.org/10.13182/NSE60-A29078
Irradiation of Uranium Monocarbide
F. A. Rough, A. W. Hare, R. B. Price, S. Alfant
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 111-121
Technical Paper | doi.org/10.13182/NSE60-A29079
The Use of the Generation Time in Reactor Kinetics
Jeffery Lewins
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 122-126
Technical Paper | doi.org/10.13182/NSE60-A29080
Convergence of the Sn Method for Thermal Systems
E. Blue, H. P. Flatt
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 127-132
Technical Paper | doi.org/10.13182/NSE60-A29081
Feasibility of Radioactive Waste Disposal in Shallow Sedimentary Formations
J. Wade Watkins, F. E. Armstrong, R. J. Heemstra
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 133-143
Technical Paper | doi.org/10.13182/NSE60-A29082
Greuling-Goertzel Calculations in Heavy Water
R. J. Mack, P. F. Zweifel
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 144-146
Technical Paper | doi.org/10.13182/NSE60-A29083
A Wide-Range Neutron Detector and Monitoring Instrument
Karl G. A. Porges, Thomas E. Klippert
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 147-155
Technical Paper | doi.org/10.13182/NSE60-A29084
Statistical Analysis of Hot Channel Factors
P. A. Rude, A. C. Nelson, Jr.
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 156-161
Technical Paper | doi.org/10.13182/NSE60-A29085
Collision Probabilities and Resonance Integrals for Lattices
Wolfgang Rothenstein
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 162-171
Technical Paper | doi.org/10.13182/NSE60-A29086
Many-fold Moment Method
D. Schiff, S. Ziering
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 172-183
Technical Paper | doi.org/10.13182/NSE60-A29087
The Absorption Cross Section of Copper for Thermal Neutrons
D. J. Donahue, R. A. Bennett, D. D. Lanning
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 184-186
Technical Paper | doi.org/10.13182/NSE60-A29088
Total Neutron Cross Sections of U233 and U235 from 0.02 to 0.08 ev
O. D. Simpson, M. S. Moore, F. B. Simpson
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 187-192
Technical Paper | doi.org/10.13182/NSE60-A29089
Total Cross Sections of Ti, V, Y, Ta, and W
R. E. Schmunk, P. D. Randolph, R. M. Brugger
Nuclear Science and Engineering | Volume 7 | Number 2 | February 1960 | Pages 193-197
Technical Paper | doi.org/10.13182/NSE60-A29090
Measurement of Air Blast Effects from Simulated Nuclear Reactor Core Excursions
Wendell C. Olson, Richard J. Larson, Harry Goldstein
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 199-209
Technical Paper | doi.org/10.13182/NSE60-A25703
The Decay of a Thermalized Neutron Pulse
Mark Nelkin
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 210-216
Technical Paper | doi.org/10.13182/NSE60-A25704
Methods and Cross Sections for Calculating the Fast Effect
Morton R. Fleishman, Harry Soodak
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 217-227
Technical Paper | doi.org/10.13182/NSE60-A25705
Neutron Absorption by Control Rods of Varying Transparency
H. Überall
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 228-234
Technical Paper | doi.org/10.13182/NSE60-A25706
A Useful Analogy for Single-Group Neutron Diffusion Theory
James R. Melcher
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 235-239
Technical Paper | doi.org/10.13182/NSE60-A25707
Slowing Down of Neutrons in Graphite Close to Thermal Equilibrium
L. S. Kothari, P. G. Khubchandani
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 240-244
Technical Paper | doi.org/10.13182/NSE60-A25708
Correlation of Burnout Heat-Flux Data at 2000 psia
Donald W. Bell
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 245-251
Technical Paper | doi.org/10.13182/NSE60-A25709
Calculation of the Effective Resonance Integral of U238
A. R. Vernon
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 252-259
Technical Paper | doi.org/10.13182/NSE60-A25710
Comparison Theorems for the Estimation of Average Collision Probabilities. II
Lawrence Dresner
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 260-262
Technical Paper | doi.org/10.13182/NSE60-A25711
Experimental Check of a Monte Carlo-Calculated Distribution of Resonance Neutron Capture in a Gold Rod
Judson Hardy, Jr., G. G. Smith, D. Klein
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 263-267
Technical Paper | doi.org/10.13182/NSE60-A25712
The Time-Dependent Importance of Neutrons and Precursors
Nuclear Science and Engineering | Volume 7 | Number 3 | March 1960 | Pages 268-274
Technical Paper | doi.org/10.13182/NSE60-A25713
Static and Dynamic Multiplication Factors and Their Relation to the Inhour Equation
E. E. Gross, J. H. Marable
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 281-291
Technical Paper | doi.org/10.13182/NSE60-A25718
Slowing Down of Neutrons
T. Teichmann
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 292-294
Technical Paper | doi.org/10.13182/NSE60-A25719
Velocity Dependent Neutron Transport Theory
W. R. Conkie
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 295-303
Technical Paper | doi.org/10.13182/NSE60-A25720
On the Theory of the Diffusion Cooling Effect in Homogeneous and Heterogeneous Assemblies
W. Häfele, L. Dresner
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 304-312
Technical Paper | doi.org/10.13182/NSE60-A25721
Transient Piston Ring Wear in Automotive Engines Using Fe59
James J. Gumbleton, Farno L. Green, William J. Mayer
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 313-319
Technical Paper | doi.org/10.13182/NSE60-A25722
Continuous Counting of Gamma Rays from Hot Radioactive Liquids
Farno L. Green, A. Somerville
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 320-322
Technical Paper | doi.org/10.13182/NSE60-A25723
Isolation of Carrier-Free Mn54 and I125 from Cyclotron Targets
H. T. Russell
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 323-324
Technical Paper | doi.org/10.13182/NSE60-A25724
Cyclotron Targets Using Enriched Stable Isotopes
P. S. Baker, F. R. Duncan, L. O. Love
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 325-326
Technical Paper | doi.org/10.13182/NSE60-A25725
The Fission Gas Problem for Mobile Fuel Fast Reactors
Frederick G. Hammitt, Evan C. Kovacic, Frederick J. Leitz
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 327-335
Technical Paper | doi.org/10.13182/NSE60-A25726
An Analysis of Neutron Flux Spatial Oscillation Due to Xenon Build-Up in a Large Power Reactor Core
Keiichi Mochizuki, Atushi Takeda
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 336-344
Technical Paper | doi.org/10.13182/NSE60-A25727
Thermal Neutron Flux Spectrum in a Medium with a Temperature Discontinuity
D. A. Kottwitz
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 345-354
Technical Paper | doi.org/10.13182/NSE60-A25728
Neutron Energy Spectrum Measurements in Unmoderated Assemblies
G. J. Fischer
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 355-362
Technical Paper | doi.org/10.13182/NSE60-A25729
Diffusion of Intermediate Energy Neutrons into a Thick Resonance Absorber
H. H. Hummel, D. Meneghetti
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 363-368
Technical Paper | doi.org/10.13182/NSE60-A25730
Relationships between Reactivity Changes, Buckling Changes, and Periods in a Heavy Water Reactor
B. S. Finn
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 369-376
Technical Paper | doi.org/10.13182/NSE60-A25731
Considerations in the Design of a Nuclear Rocket
John J. Newgard, Myron M. Levoy
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 377-386
Technical Paper | doi.org/10.13182/NSE60-A25732
Maximizing Production of Radioisotopes in a Cyclotron
Farno L. Green, John A. Martin
Nuclear Science and Engineering | Volume 7 | Number 4 | April 1960 | Pages 387-391
Technical Paper | doi.org/10.13182/NSE60-A25733
Absorption Cross Section of Graphite
P. F. Nichols
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 395-399
Technical Paper | doi.org/10.13182/NSE60-A25736
The Effects of Internal Heat Generation on Heat Transfer in Thin Fins
W. S. Minkler, W. T. Rouleau
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 400-406
Technical Paper | doi.org/10.13182/NSE60-A25737
The Reactivity of Natural UO2 Irradiated to 6 × 1021 n/cm2
S. B. Gunst, E. D. McGarry, J. J. Scoville
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 407-418
Technical Paper | doi.org/10.13182/NSE60-A25738
On the Validity of the Second Fundamental Theorem in a Medium with Anisotropic Scattering
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 419-424
Technical Paper | doi.org/10.13182/NSE60-A25739
Elastic-Plastic Thermal Stresses in Tubes Subjected to Uniform Heat Generation Evaluation of Experimental Results Obtained Using Graphite Tubes
T. Kammash
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 425-434
Technical Paper | doi.org/10.13182/NSE60-A25740
An Investigation of Effective Neutron Temperatures
W. P. Stinson, L. C. Schmid, R. E. Heineman
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 435-441
Technical Paper | doi.org/10.13182/NSE60-A25741
The Density of Liquid Lead and of Dilute Solutions of Nickel in Lead
S. W. Strauss, L. E. Richards, B. F. Brown
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 442-447
Technical Paper | doi.org/10.13182/NSE60-A25742
Fission-to-Indium Age in Water
D. B. Lombard, C. H. Blakchard
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 448-453
Technical Paper | doi.org/10.13182/NSE60-A25743
Resonance Capture of Neutrons in Nonheavy Absorbers
W. Rothenstein, J. Chernick
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 454-457
Technical Paper | doi.org/10.13182/NSE60-A25744
Experimental Investigations of Pressure Drop through Interrupted-Plate-Type Fuel Elements
B. W. LeTourneau, R. E. Grimble
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 458-467
Technical Paper | doi.org/10.13182/NSE60-A25745
On the Temperature Dependence of the Thermal Neutron Flux Kernel
D. C. Anderson
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 468-471
Technical Paper | doi.org/10.13182/NSE60-A25746
A Simplified Theory of Pile Noise
Charles Erwin Cohn
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 472-475
Technical Paper | doi.org/10.13182/NSE60-4
Surface Perturbation Theory
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 481-486
Technical Paper | doi.org/10.13182/NSE60-A25754
Gas Bubble Formation in Irradiated Plastics and Reactor Fuels
G. G. Bentle
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 487-495
Technical Paper | doi.org/10.13182/NSE60-A25755
Flat Flux by Nonuniform Moderation
Jack M. Ravets, John R. Lamarsh
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 496-501
Technical Paper | doi.org/10.13182/NSE60-A25756
Parameters of the Lu176 Neutron Resonance at 0.142 ev
Joseph P. Roberge, Vance L. Sailor
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 502-504
Technical Paper | doi.org/10.13182/NSE60-A25757
The Black Void Reactor Concept
C. O. Muehlhause
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 505-507
Technical Paper | doi.org/10.13182/NSE60-A25758
In-Pile Loop Study of UO2-NaK Slurry
R. D. Carlson
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 508-513
Technical Paper | doi.org/10.13182/NSE60-A25759
Measurements of Parameters Leading to P28, f, and ϵ in Light Water Moderated 4.48% and 2.73% Enriched Lattices
Victor E. Grob, E. Santandrea, Hilmar Ritz
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 514-524
Technical Paper | doi.org/10.13182/NSE60-A25760
The Prediction of Steam Volume Fractions in Boiling Systems
J. F. Marchaterre, M. Petrick
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 525-532
Technical Paper | doi.org/10.13182/NSE60-A25761
Boundedness and Stability in Nonlinear Reactor Dynamics
Elias P. Gyftopoulos, Jacques Devooght
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 533-540
Technical Paper | doi.org/10.13182/NSE60-A25762
An H2O-D2O Moderated Reactor
Norman P. Klug, P. F. Zweifel
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 541-544
Technical Paper | doi.org/10.13182/NSE60-A25763
Breeding Ratio in U233 and Pu239 Fueled Reactors
Melvin M. Levine
Nuclear Science and Engineering | Volume 7 | Number 6 | June 1960 | Pages 545-551
Technical Paper | doi.org/10.13182/NSE60-A25764
